ML20082G944

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Proposed Tech Spec 3.1.2.6 Re RCS Temp & Pressure
ML20082G944
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 08/14/1991
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20082G943 List:
References
NUDOCS 9108220134
Download: ML20082G944 (5)
v • d • e


Text

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9 PROPOSED TECHNICAL SPECIFICATION CIIANGES 9108220134 910814 PDR ADOCK 05000313 P

PDR

3.1.2 l'r.p s s u riztLt ion _. _ llea t upa and Cooldnwn Limit atlong Sp.eci fica tjan 3.1.2.1 Ilydro Tests For thermal steady stato system hydro tests, the system may be pressurized to the limits set forth in Specification 2.2 when there are fuel assemblies in the coro, under the provisions of 3.1.2.3, and to ASMP. Codo limits when no fuel assemblies are present provided the reacter coolant system limits are to the right of and below the limit lino in Figure 3.1.2-1.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

3.1.2.2 Lenk Tests Leak tests required by Specification 4.3 shall be conducted under the provision of 3.1.2.3.

The provisions of Specification 3.0.3 are not applicable.

3.1.2.3 The reactor coolant pressure and the system hoatup end cooldown rates (with the exception'of the pressurizer) shall be limited in accordance with Figure 3.1.2-2 and Figure 3.1.2-3, and.

are as follows:

lleatup:

A110wablo combinations of pressure and temperature shall be to the right of and below the limit lino in Figure 3.1.2-2.

The heatup rates shall not excead those shown in_Figuro 3.1.2-2.

Cooldown:

Allowabic combinations of pressure and tomperature for a specific-cooldown shall be to the right of and below the limit lino in Figure 3.1.2-3.

Cooldown ratos shall not exceed those shown in-Figuro 3.1.2-3, 3.1.2.4 The secondary side of the steam generator shall not be pressurized abovo 200 psig if the temperature of-the steam generator shell is below 100F.=

3.1.2.5 The pressurizer heatup and cooldown rates shall not exceed 100F/hr. The spray shall not be used if the temperaturo difference between the pressurizer and the spray fluid is greater than 430F.

3.1'.2.6 With the limits 'of Specifications 3.1.2.3 or_3.1.2.4 or 3.1.2.5 exceeded, restore the temperature and/or pressure to-within the limit within 30 minutos; perform an engineering.

evaluation to determine the effects of the out-of-limit condition on the fracture toughness properties of-the Reactor 9 Coolant-System; determine that-the Reactor Coolant' System remains acceptable for continued operations or be in at least flor. STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the RCS Tavg to less than 200F, while maintainin,; RCS temperature and pressure ~bolow the curvo, within the folleving 30 hourn.

. Amendment No. 22, 26, 57 18

k NNOTES-8 NTA6kCCEPTABLE PRESSURE TEMPERATURE COMBINATONS ARE BELOW AND TO THE RIGHT OF THE LIMIT CURVE (S). THE UMIT CURVES INCLUDE 34E LIMIT NG PRESSURE

[

2400 DIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE MEASUREMENT AND THE PRESSURE ON THE REACTOR VESSEL REGION CONTROLUNG THE UMfT CURVE. THEY 3

K P

ARE MQI ADJUSTED FOR POSSIBLE INSTRUMENT ERROR AND THESE CURVES SHALL MOO MQIBE USED FOR OPERATION.

2. APPUCABLE FOR HEATUP RATES OF s 50 DEG F,hR.

g E.

2 3. APPUCABLE FOR COOLDOWN RATES OF:

T2280 DEG F 100 DEG FiHR (550 DEG F IN ANY 1/2 HOUR PEROD) er 8

~

280 DEG F > T2150 DEG F 50 DEG F,HR (s25 DEG F IN ANY 1/2 HOUR PEROD) fp El T<150 DEG F 25 DEG FiHR (s25 DEG F IN ANY 1 HOUR PEROD) /J

$m

{ 4. REACTOR COOLANT PUMP RESTRICTONS:

16 gg NONE.

.y E *i 1400

~

Ez 21 n

O f$1200 H

~

,c 2%

u-c:

PRESS TEMP O

3 G

A 388 70 3

600 5

B 422 100 E

~

C 455 125 D

461 150 600

[E I

E 527 170 C

D F

F 541 205 B

400 g

G 822 220 l

H 1115 255 8

1382 280 203

~

J 1763 305 K

2286 330 L

2500 339 A

i i i i i ! i i i.

I l i i l-i iii

. I i i i i i i i i i i i i i E

O 50 100 150 200 250 300 350 Indicated Reactor Coc! ant inlet Temperature, 'F y

REACTOR COOLANT SYSTEM INSERVICE HYDROSTATIC TEST HEATUP AND COOLDOWN a

LIMITATIONS APPLICABLE FOR FIRST 15.0 EFFECTIVE FULL POWER YEARS

2600 3

9 a

g 24M

- NOTES:

2

1. THE ACCEPTABLE PRESSURE TEMPERATURE COMBINATIONS ARE BELOW AND TO THE y

a y

RIGHT OF THE LIMIT CURVE (S). THE LIMIT CURVES INCLUDE THE LIMITING PRESSURE 7

7 o4 22M DIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE MEASUREMENT AND THE

/

[

PRESSURE ON THE REACTOR VESSEL REGION CONTROLLING THE LIMIT CURVE. THEY

(

D ARE HQI ADJUSTED FOR POSSIBLE INSTPUMENT ERROR AND THESE CURVES SHALL j 2000

.50 7

101BE USED FOR OPERATION..

E.

g

2. APPLICAB'_E FOR HEATUP RATES OF $ 50 DEG F/HR.

/

1800 Ei E

3. WHEN THE DECAY HEAT REMOVAL SYSTEM IS OPERATING WITH NO RG E

PUMPS OPERATING. THE INDICATED DHR SYSTEM RETURN TEMPERA FURE

/

o.1600 7

TO THE REACTOR VESSEL SHALL BE USED.

$, F

4. REACTOR COOLANT PUMP RESTRICTIONS:

/

} g 4"

7 NONE.

/

g g 1200

--- S. CURVE N-O-P-O IS THE CRITICALITY CURVE [

bb 2

PAESS 7EMP j

m POINT (pss)

(deg F) o li A

331 70 M ~ 1000 g

B 331 125 C

as9 150 g

D 415 170 y

g 2

E 498 195 8

800 F

541 204

-j H

G 541 230 H

695 234 1

809 255 600

/

J 1011 250 E

y K

1234 300 D

F G

400 C

L 37cs 333 A

ts e

M 2250 355 g

N O

340 O

1234 340 P

1708 370 N

[

O 2250 395 0

~

2' 1 I I I I i i i i i i i i I i l I i i I i i I I I i i l i I I c

0 50 100 150 200 250 300 350 400 Indicated Reactor Coolant inlet Temperature, *F o

REACTOR COOLANT SYSTEM NORMAL OPERATION - HEATUP LIMITATIONS N

APPLICABLE FOR FIRST 15.0 EFFECTIVE FULL POWER YEARS

i I

i i

i i

y g

NOTES-1.THE ACCEPTABLE PRESSURE TEMPERATURE COMB: NATIONS ARE BELOW AND TO THE 2400 g

RIGHT OF THE LIMIT CURVE (S). THE UMIT CURVES INCLUDE THE LIMITING PRESSURE 3

DIFFERENTIAL BETWEEN THE POINT OF SYSTEM PRESSURE MEASUREMENT AND THE K

PRESSURE ON THE REACTOR VESSEL REGION CONTROLUNG THE LIMF CURVE. THEY 7

P 2200 ARE LM ADJUSTED FOR POSSIBLE INSTRUMENT ERROR AND THESE CURVES SHALL

}

J

~

NOI BE USEO FOR OPERATON.

P

2. APPUCABLE FOR COOLDOWN RATES OF:

E.

T2280 DEG F 100 DEG F/HR (s50 DEG F IN ANY 1/2 HOUR PERIOD) er 1800 280 DEG F > T2150 DEG F 50 DEG F/HR (s25 DEG F IN ANY 1/2 HOUR PERIOD /

,Ei T<150 DEG F 2S DEG F/HR (s25 DEG F IN ANY 1 HOUR PEROD' e

[ - 1600

3. WHEN THE DECAY HEAT REMOVAL SYSTEM IS OPERATING WITH NO RC E g-PUMPS OPERATING, THE INDICATED DHR SYSTEM RETURN TEMPERATURE

/

gg TO THE REACTOR VESSEL SHALL BE USED.

b

4. A MAX! MUM STEP TEMPERATURE CHANGE OF 35 DEG F IS ALLOWABLE

~$

WHEN REMOVING ALL RC PUMPS FROM OPERATON WITH THE DHR E

3 ro 8

SYSTEM OPERATING. THE STEP TEMPERATURE CHANGE IS 8

o $ 1200 DEFINED AS THE RC TEMPERATURE (PROR TO STOPP!NG ALL a-j~g RC PUMPS) MINUS THE DHR RETURN TEMPERATURE TO 1000 THE REACTOR VESSEL (AFTER STOPPING ALL RC PUMPS)

M THE 50 DEG FMR COOLDOWN RATE IS ALLOWABLE PRESS TEMP c

BOTH BEFORE AND AFTER THE STEP TEMPERATUR POINT (psg)

(deg F) 800 CHANGE.

/

/

A 260 70 g

B 287 100 l

5

5. REACTOR COOLANT PUMP RESTR!CTIONS:

G C

312 125 600 NONE.

D 316 150 F

E 366 170 t

E f

F 430 195 400 G

589 220 C

U f B

H 907 2S5 3

-H 1

1192 280 200 J

2078 330 K

2250 339 O

k 0

50 100 150 200 250 300 350 400 Indicated Reactor Coolant inlet Temperature. *F 9

REACTOR COOLANT SYSTEM NORMAL OPERATON - COOLDOWN UMITATONS APPUCABLE FOR FIRST 15.0 EFFECTIVE FULL POWER YEARS u.

-

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